ML20050C956

Application to Amend License DPR-57,changing Tech Spec Operability Requirements for HPCI Sys & Reactor Core Isolation Cooling Sys,Per 10CFR50.90 & 10CFR50.59(c)(1)

ML20050C956
Person / Time
Site:	Hatch
Issue date:	04/05/1982
From:	Beckham J GEORGIA POWER CO.
To:	Office of Nuclear Reactor Regulation
Shared Package
ML20050C957	List: ML20050C956 ML20050C959
References
TAC-48294, TAC-54495, NUDOCS 8204090448
Download: ML20050C956 (3)

Text

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Director of Nuclear Reactor Regulation , CEmpg U. S. Nuclear Regulatory Commission B- C Washington, D. C. 20555 ~

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NRC DOCKET 50-321 OPERATING LICENSE DPR-57 EDWIN I. HATCH NUCLEAR PLANT UNIT 1

• HPCI AND RCIC LCO CHANGE PROPOSAL Gentlemen:

In accordance with the provisions of 10 CFR 50.90 as required by the provisions of 10 CFR 50.59(c)(1), Georgia Power Company (GPC) hereby proposes an amendment to the Edwin I. Hatch Unit 1 Technical Specifications (Appendix A to the Operating License). This amendment would change the requirements for the High Pressure Coolant Injection (HPCI) system and the Reactor Core Isolation Cooling (RCIC) system to require the systems to be operable when reactor vessel pressure is greater than 150 psig.

The Hatch Unit 1 Technical Specifications currer tly specify that the HPCI and RCIC systems shall be operable above 113 psig reactor pressure.

However, this requirement differs from that in the Hatch Unit 2 Technical Specifications which requires HPCI and RCIC to be operable above 150 psig reactor pressure. Consequently, a change is reauested to eliminate this inconsistency between the two units. The basis fur this change is provided in the following discussion.

, Use of 150 psig as the lower operability limit for HPCI and RCIC is l technically supported by the perfomance specifications given for these systems in the Hatch Unit 1 FSAR. As can be seen in tne design data table

! and the process flow diagram for HPCI, Table 6.3-1 and Figure 6.4-1, and for RCIC, Table 4.7-1 and Figure 4.7-3, the minimum pressure for the low pressure accident mode of operation of each system is greater than o(~ equal to 150 psig. These same operability requirements are also discussed in the Hatch Unit 2 FSAR. Furthennore, the current Hatch Unit 1 Technical l Specification surveillance requirements for normal operational tests of HPCI and RCIC (Sections 4.5.D.l.b, and 4.5.E.1.b) state that flow rate tests will be conducted at normal reactor operating pressure and at 150 psig reactor pressure.

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Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission April 5, 1982 Page Two The basis for RCIC contained in Unit 1 Technical Specifications Section 3.5.E.1 states that ~ reduced flow is required for certain (unidentified) events at reactor pressures between 113 psig and 150 psig. GE licensing has stated that there are no requirements for any RCIC flow within this pressure range and that this basis statement may be deleted without raising an unreviewed safety question.

Application of these proposed Technical Specification changes would not constitute on unreviewed safety question as determined by the Plant Review Board and the Safety Review Board. The probability of occurrence or the consequences of an accident or malfunction of safety-related equipment are not increased above those analyzed in the FSAR, because the Hatch Unit 1 FSAR performance specifications for HPCI and RCIC does not specify operation of these systems below 150 psig reactor pressure. The possibility of an accident or malfunction different from those analyzed in the FSAR does not result from this change, since the system need not be operated in a new or different manner. The margin of safety as analyzed in Technical Specifications is not reduced because the Hatch Unit 1 Technical Specifications do not require surveillance testing below 150 psig reactor pressure for HPCI and RCIC. Furthermore, the Low Pressure Coolant Injection System, Automatic Depressurization System, and Core Spray System, all are still required to be operational in the range of reactor pressure between 113 psig and 150 psig.

Instructions for incorporation of these changes along with copies of affected Technical Specification pages are emlosed.

Included with this proposal is a determination of amendment class. We have determined this to be one Class III amendment, and have enclosed the appropriate payment.

J. T. Beckham, Jr. states that he is Vice President of Georgia Power Company and is authorized to execute this oath on behalf of Georgia Power Company, and that to the best of his knowledge and belief the facts set forth in this letter are true.

GEORGIA POWER C0r4'ANY By . ,

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[/ J. T. Beckham, Jrf Sworp-t ngpubscribed befo e this i day of April, 1982 a r-> < - J . . ] <LR /

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Georgia Powerkn Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commissien April 5,1982 Page Three Attachment xc: M. Manry R. F. Rogers, III J. P. O'Reilly (NRC - Region II) i